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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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Oklo completes end-to-end demonstration of advanced fuel recycling
Oklo Inc. has announced that it has completed the first end-to-end demonstration of its advanced fuel recycling process as part of an ongoing $5 million project in collaboration with Argonne and Idaho National Laboratories. Oklo’s goal: scaling up its fuel recycling capabilities to deploy a commercial-scale recycling facility that would increase advanced reactor fuel supplies and enhance fuel cost effectiveness for its planned sodium fast reactors.
B. K. Kamboj, S. M. Ghiaasiaan, S. I. AbdeL-Khalik
Nuclear Technology | Volume 105 | Number 3 | March 1994 | Pages 381-394
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34938
Articles are hosted by Taylor and Francis Online.
A phenomenological model is developed for the transient thermal-hydraulic processes on the secondary side of a once-through steam generator during auxiliary feedwater (AFW) injection. Detailed modeling of the thermal-hydraulic processes above the top tube support plate (TSP) is particularly emphasized. The nonuniform distribution of the AFW on the secondary-side tubes is represented by dividing the secondary side into a number of tube groups. For each tube group, the quasi-steady-state conservation equations representing the flow of a falling liquid film and steam on the secondary side and the primary coolant on the primary side are numerically solved for each time step, thereby providing the axial variation of flow rates and temperatures in the primary and secondary sides. Modeled processes include cooling due to the impingement of the AFW jet on the tubes, the forced convection/boiling heat transfer at the liquid film-tube interface, evaporation and condensation at the film-gas interphase, countercurrent flow limitation in the TSP passages, and the formation of a swollen two-phase pool above the top TSP. The aforementioned model for the thermal-hydraulic phenomena above the top TSP is incorporated into a transient model for the entire steam generator where the secondary side is divided into four regions. Global conservation equations representing the transient behavior of each region are numerically solved. Model predictions are compared with a typical test from the Multiloop Integral System Test experiments. Parametric and sensitivity calculations are also reported.